US4582676A - Coating a uranium dioxide nuclear fuel with a zirconium diboride burnable poison - Google Patents

Coating a uranium dioxide nuclear fuel with a zirconium diboride burnable poison Download PDF

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Publication number
US4582676A
US4582676A US06/468,743 US46874383A US4582676A US 4582676 A US4582676 A US 4582676A US 46874383 A US46874383 A US 46874383A US 4582676 A US4582676 A US 4582676A
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layer
niobium
zirconium diboride
burnable poison
uranium dioxide
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US06/468,743
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Walston Chubb
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Westinghouse Electric Corp
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Westinghouse Electric Corp
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Assigned to WESTINGHOUSE ELECTRIC CORPORATION; A CORP OF PA. reassignment WESTINGHOUSE ELECTRIC CORPORATION; A CORP OF PA. ASSIGNMENT OF ASSIGNORS INTEREST. Assignors: CHUBB, WALSTON
Priority to US06/468,743 priority Critical patent/US4582676A/en
Priority to ZA84504A priority patent/ZA84504B/en
Priority to DE3402192A priority patent/DE3402192A1/en
Priority to GB08402535A priority patent/GB2137012B/en
Priority to SE8400596A priority patent/SE458810B/en
Priority to IT19596/84A priority patent/IT1178463B/en
Priority to CH752/84A priority patent/CH664036A5/en
Priority to BE0/212429A priority patent/BE898971A/en
Priority to KR1019840000825A priority patent/KR910005068B1/en
Priority to FR8402600A priority patent/FR2541495B1/en
Priority to JP59030497A priority patent/JPS59159089A/en
Publication of US4582676A publication Critical patent/US4582676A/en
Application granted granted Critical
Priority to GB08616520A priority patent/GB2177250B/en
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/16Details of the construction within the casing
    • G21C3/20Details of the construction within the casing with coating on fuel or on inside of casing; with non-active interlayer between casing and active material with multiple casings or multiple active layers
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/02Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect
    • G21C7/04Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect of burnable poisons
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Definitions

  • the present invention relates generally to burnable poisons for nuclear reactors and, more particularly, to a method for coating a uranium dioxide nuclear fuel with a zirconium diboride burnable poison and to a zirconium diboride coated uranium dioxide nuclear fuel.
  • nuclear fuel may have various shapes such as plates, columns, and even fuel pellets disposed in end-to-end abutment within a tube or cladding made of a zirconium alloy or stainless steel.
  • the fuel pellets contain fissionable material, such as uranium dioxide or mixed uranium-plutonium dioxide.
  • the fuel rods are usually clad with a zirconium alloy and are usually grouped together to form a fuel assembly.
  • the fuel assemblies are arranged together to constitute the core of a nuclear reactor.
  • the process of nuclear fission involves the disintegration of the fissionable nuclear fuel material into two or more fission products of lower mass number.
  • the process also includes a net increase in the number of available free neutrons which are the basis for a self-sustaining reaction.
  • the fuel assembly with fissionable material must ultimately be replaced due to depletion.
  • Such neutron-capturing elements are usually designated as "burnable poisons" if they have a high probability (or cross section) for absorbing neutrons while producing no new or additional neutrons or changing into new poisons as a result of neutron absorption.
  • burnable poisons are progressively reduced in amount so that there is a compensation made with respect to the concomitant reduction in the fissionable material.
  • the life of a fuel assembly may be extended by combining an initially larger amount of fissionable material as well as a calculated amount of burnable poison.
  • burnable poison compensates for the larger amount of fissionable material during the early life of the fuel assembly, but progressively less poison captures neutrons during the latter life of the fuel assembly, so that a long life at relatively constant fission level is assured for the fuel assembly. Accordingly, with a fuel assembly containing both fuel and burnable poison in carefully proportioned quantity, an extended fuel assembly life can be achieved with relatively constant neutron production and reactivity.
  • Burnable poisons which may be used are boron, gadolinium, samarium, and europium, which upon the absorption of neutrons result in isotopes of sufficiently low neutron capture cross section so as to be substantially transparent to neutrons.
  • Burnable poisons are used either uniformly mixed with the fuel (i.e., distributed poison) or are placed discretely as separate elements in the reactor, so arranged that they burn out or are depleted at about the same rate as the fuel.
  • distributed poison i.e., distributed poison
  • the net reactivity of the core is maintained relatively constant over the active life of the core.
  • U.S. Pat. No. 3,427,222 discloses a uranium dioxide fuel pellet substrate coated with a mixture of uranium dioxide and a zirconium diboride burnable poison applied by a plasma-spraying technique (see column 4, "Example I”). That patent also disclosed a uranium dioxide fuel pellet substrate coated with the burnable poison boron applied by chemical vapor deposition, and the patent noted that the deposition rate was slow at low temperatures while the coating was not as adherent at high temperatures (see column 5, “Example III”).
  • a nuclear fuel contained in an aluminum can may be coated with a layer of niobium to prevent the fuel from reacting with the can (British Pat. No. 859,206; page 1; lines 12-30). It is also known that minute nuclear fuel particles, such as uranium dioxide particles, may be coated with a single layer or several layers of the same or different non-poison materials, including niobium, for such purposes as protecting the fuel from corrosion and helping to retain the products of fission.
  • the coatings may be applied by various techniques, such as depositing from a vapor of the coating material, depositing from a decomposing vapor, and electroplating (British Pat. No. 933,500).
  • Japanese Pat. No. 52-3999 discloses a nuclear fuel first coated with a thin layer of a material (such as niobium) to absorb fission fragments and then coated with a main coating material (such as Zircaloy).
  • a material such as niobium
  • a main coating material such as Zircaloy
  • the present inventor was aware of unsuccessful attempts to coat uranium dioxide fuel pellet substrates with a zirconium diboride burnable poison by chemical vapor deposition in which the zirconium diboride adhered poorly to the uranium dioxide, resulting in spalling.
  • the invention is directed towards a method for coating a zirconium diboride containing burnable poison on a uranium dioxide containing nuclear fuel.
  • the nuclear fuel is coated with a layer containing niobium.
  • the niobium-containing layer is coated by chemical vapor deposition with a layer containing the burnable poison.
  • the invention is also directed towards a zirconium diboride coated uranium dioxide nuclear fuel having a layer of niobium between the uranium dioxide substrate and the zirconium diboride layer.
  • FIG. 1 is a longitudinal sectional view of a fuel rod having a plurality of coated pellets of uranium dioxide.
  • FIG. 2 is a transverse sectional view along the lines II--II of FIG. 1.
  • Nuclear fuel includes uranium in the form of uranium dioxide or mixed uranium-plutonium dioxide pellets each having a generally cylindrical configuration with an approximately one-third inch diameter and an approximately one-half inch length.
  • Desirable zirconium diboride burnable poison coating thicknesses on the fuel pellets include a thickness of between about 8 and 16 microns (and preferably of between about 9 and 10 microns which corresponds to a target boron-10 loading of generally 1.5 mg per lineal inch).
  • Chemical vapor deposition is a relatively fast coating process when compared with other techniques such as sputtering. Attempts were known to coat zirconium diboride on uranium dioxide pellets by CVD using zirconium tetrachloride and boron trichloride. The coating rate seemed slow at about 700° C. At about 800° C. the coating rate was satisfactory but when the coating cooled, it spalled. The maximum crack-free coating was about 2 to 3 microns which is far short of the desired 9 to 10 microns.
  • a fuel rod 10 for use in a nuclear reactor fuel assembly, includes an elongated tube 12 having a top end plug 14 and a bottom end plug 16 providing an enclosed chamber 18 in which a plurality of fissionable fuel pellets 20 are placed in end-to-end abutment biased against the bottom end plug 16 by the action of a spring 22.
  • the pellet 20 diameter is slightly less than that of the tube 12 and forms a clearance space 24. Both the spring 22 and clearance space 24 accommodate any thermal expansion of the pellets 20 during operation.
  • niobium layer 28 of niobium is bondably deposited on the nuclear fuel pellet substrate 26, and then a layer 30 of zirconium diboride burnable poison is bondably deposited on the niobium layer 28 by chemical vapor deposition.
  • the niobium layer 28 may be applied by conventional means, as previously mentioned, and preferably by relatively fast chemical vapor deposition utilizing niobium pentachloride.
  • the preferred thickness of the niobium layer 28 is between about 3 and 6 microns. Even with a slower conventional non-CVD coating procedure for the niobium layer, the overall coating time for a non-CVD niobium layer plus the CVD zirconium diboride layer will be less than utilizing a sngle step non-CVD zirconium diboride technique, remembering that a single step CVD zirconium diboride layer with the desired thickness will spall.
  • Uranium dioxide fuel pellet substrates 26 were coated by conventional CVD techniques first with niobium and then with zirconium diboride utilizing a vertical tube surrounding vertically stacked fuel pellets.
  • the gaseous CVD precursors niobium pentachloride for the niobium layer 28, and zirconium tetrachloride and boron trichloride for the zirconium diboride layer 30
  • the fuel pellet substrates 26 had been cleaned by light sanding, repeated ultrasonic cleaning in distilled water, and vacuum drying. Thermocouples were mounted on the walls of the tube.
  • the pellet substrates 26 were heated to a thermocouple-measured predetermined wall temperature by an upper furnace while the precursor gases were preheated to a thermocouple-measured preselected wall temperature by a lower furnace. Crack-free coatings were obtained under various conditions as summarized in Table 1.
  • gaseous niobium pentachloride was prepared by vaporizing niobium pentachloride in a hydrogen stream
  • gaseous zirconium chloride was prepared by reacting hydrogen chloride and zirconium and carrying the reaction products in a hydrogen stream.
  • the method of the invention is used to circumferentially surround (i.e., coat only the cylindrical wall of) the uranium fuel pellet substrates 26 with the niobium layer 28 and then the zirconium diboride layer 30.
  • the method of the invention may be used to produce a fuel pellet 20 having a uranium dioxide containing substrate 26 covered with a niobium containing layer 28 covered with a zirconium diboride containing layer 30, it is preferred that the uranium dioxide containing substrate 26, the niobium containing layer 28, and the zirconium diboride containing layer 30 consist essentially of uranium dioxide, niobium, and zirconium diboride, respectively.
  • the terminology "uranium dioxide containing nuclear fuel” includes mixed uranium-plutonium dioxide.

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  • Engineering & Computer Science (AREA)
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  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
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Abstract

A method for coating a uranium dioxide nuclear fuel with a zirconium diboride burnable poison. First, a layer of niobium is bonded to the nuclear fuel. Then, a layer of zirconium diboride is deposited by chemical vapor deposition on the niobium layer. A zirconium diboride coated nuclear fuel having a layer of niobium between a uranium dioxide substrate and the zirconium diboride layer also is disclosed.

Description

BACKGROUND OF THE INVENTION
The present invention relates generally to burnable poisons for nuclear reactors and, more particularly, to a method for coating a uranium dioxide nuclear fuel with a zirconium diboride burnable poison and to a zirconium diboride coated uranium dioxide nuclear fuel.
It is known that nuclear fuel may have various shapes such as plates, columns, and even fuel pellets disposed in end-to-end abutment within a tube or cladding made of a zirconium alloy or stainless steel. The fuel pellets contain fissionable material, such as uranium dioxide or mixed uranium-plutonium dioxide. The fuel rods are usually clad with a zirconium alloy and are usually grouped together to form a fuel assembly. The fuel assemblies are arranged together to constitute the core of a nuclear reactor.
It is well known that the process of nuclear fission involves the disintegration of the fissionable nuclear fuel material into two or more fission products of lower mass number. Among other things the process also includes a net increase in the number of available free neutrons which are the basis for a self-sustaining reaction. When a reactor has operated over a period of time, the fuel assembly with fissionable material must ultimately be replaced due to depletion. Inasmuch as the process of replacement is time consuming and costly, it is desirable to extend the life of a given fuel assembly as long as practically feasible. For that reason, deliberate additions to the reactor fuel of parasitic neutron-capturing elements in calculated small amounts may lead to highly beneficial effects on a thermal reactor. Such neutron-capturing elements are usually designated as "burnable poisons" if they have a high probability (or cross section) for absorbing neutrons while producing no new or additional neutrons or changing into new poisons as a result of neutron absorption. During reactor operation the burnable poisons are progressively reduced in amount so that there is a compensation made with respect to the concomitant reduction in the fissionable material.
The life of a fuel assembly may be extended by combining an initially larger amount of fissionable material as well as a calculated amount of burnable poison. During the early stages of operation of such a fuel assembly, excess neutrons are absorbed by the burnable poison which undergoes transformation to elements of low neutron cross section which do not substantially affect the reactivity of the fuel assembly in the latter period of its life when the availability of fissionable material is lower. The burnable poison compensates for the larger amount of fissionable material during the early life of the fuel assembly, but progressively less poison captures neutrons during the latter life of the fuel assembly, so that a long life at relatively constant fission level is assured for the fuel assembly. Accordingly, with a fuel assembly containing both fuel and burnable poison in carefully proportioned quantity, an extended fuel assembly life can be achieved with relatively constant neutron production and reactivity.
Burnable poisons which may be used are boron, gadolinium, samarium, and europium, which upon the absorption of neutrons result in isotopes of sufficiently low neutron capture cross section so as to be substantially transparent to neutrons.
Incorporation of burnable poisons in fuel assemblies has been recognized in the nuclear field as an effective means of increasing fuel capacity and thereby extending core life. Burnable poisons are used either uniformly mixed with the fuel (i.e., distributed poison) or are placed discretely as separate elements in the reactor, so arranged that they burn out or are depleted at about the same rate as the fuel. Thus, the net reactivity of the core is maintained relatively constant over the active life of the core.
U.S. Pat. No. 3,427,222 discloses a uranium dioxide fuel pellet substrate coated with a mixture of uranium dioxide and a zirconium diboride burnable poison applied by a plasma-spraying technique (see column 4, "Example I"). That patent also disclosed a uranium dioxide fuel pellet substrate coated with the burnable poison boron applied by chemical vapor deposition, and the patent noted that the deposition rate was slow at low temperatures while the coating was not as adherent at high temperatures (see column 5, "Example III").
It is known that a nuclear fuel contained in an aluminum can may be coated with a layer of niobium to prevent the fuel from reacting with the can (British Pat. No. 859,206; page 1; lines 12-30). It is also known that minute nuclear fuel particles, such as uranium dioxide particles, may be coated with a single layer or several layers of the same or different non-poison materials, including niobium, for such purposes as protecting the fuel from corrosion and helping to retain the products of fission. The coatings may be applied by various techniques, such as depositing from a vapor of the coating material, depositing from a decomposing vapor, and electroplating (British Pat. No. 933,500).
Japanese Pat. No. 52-3999 discloses a nuclear fuel first coated with a thin layer of a material (such as niobium) to absorb fission fragments and then coated with a main coating material (such as Zircaloy). The patent apparently does not concern burnable absorber coatings, and is not relevant to the present invention.
In Dispersion Fuel Elements, an AEC Monograph by A. N. Holden published in 1967 by Gordon and Breach of New York, there is mentioned coating fuel particles in dispersion fuels to prevent interaction of the particles with the matrix and to retain fission products (page 30). Uranium dioxide coated with niobium by vapor-phase reduction is disclosed (page 48). Also disclosed is uranium dioxide coated with chromium, by vapor-phase reduction using chromium dichloride, which was deposited over a niobium undercoat (page 48).
The present inventor was aware of unsuccessful attempts to coat uranium dioxide fuel pellet substrates with a zirconium diboride burnable poison by chemical vapor deposition in which the zirconium diboride adhered poorly to the uranium dioxide, resulting in spalling.
SUMMARY OF THE INVENTION
Briefly stated, the invention is directed towards a method for coating a zirconium diboride containing burnable poison on a uranium dioxide containing nuclear fuel. First, the nuclear fuel is coated with a layer containing niobium. Then, the niobium-containing layer is coated by chemical vapor deposition with a layer containing the burnable poison. The invention is also directed towards a zirconium diboride coated uranium dioxide nuclear fuel having a layer of niobium between the uranium dioxide substrate and the zirconium diboride layer.
BRIEF DESCRIPTION OF THE DRAWINGS
The subject matter of the invention is particularly pointed out and distinctly claimed in the concluding portion of this specification. The invention, however, both as to organization and method operation, together with further advantages thereof, may best be understood by reference to the following description taken in connection with the accompanying drawings in which:
FIG. 1 is a longitudinal sectional view of a fuel rod having a plurality of coated pellets of uranium dioxide.
FIG. 2 is a transverse sectional view along the lines II--II of FIG. 1.
DETAILED DESCRIPTION OF THE INVENTION
Nuclear fuel includes uranium in the form of uranium dioxide or mixed uranium-plutonium dioxide pellets each having a generally cylindrical configuration with an approximately one-third inch diameter and an approximately one-half inch length. Desirable zirconium diboride burnable poison coating thicknesses on the fuel pellets include a thickness of between about 8 and 16 microns (and preferably of between about 9 and 10 microns which corresponds to a target boron-10 loading of generally 1.5 mg per lineal inch).
Chemical vapor deposition (CVD) is a relatively fast coating process when compared with other techniques such as sputtering. Attempts were known to coat zirconium diboride on uranium dioxide pellets by CVD using zirconium tetrachloride and boron trichloride. The coating rate seemed slow at about 700° C. At about 800° C. the coating rate was satisfactory but when the coating cooled, it spalled. The maximum crack-free coating was about 2 to 3 microns which is far short of the desired 9 to 10 microns.
Applicant's invention permits a relatively thick CVD zirconium diboride coating on a uranium dioxide fuel pellet. In applicant's invention, as seen in FIGS. 1 and 2, a fuel rod 10, for use in a nuclear reactor fuel assembly, includes an elongated tube 12 having a top end plug 14 and a bottom end plug 16 providing an enclosed chamber 18 in which a plurality of fissionable fuel pellets 20 are placed in end-to-end abutment biased against the bottom end plug 16 by the action of a spring 22. The pellet 20 diameter is slightly less than that of the tube 12 and forms a clearance space 24. Both the spring 22 and clearance space 24 accommodate any thermal expansion of the pellets 20 during operation. In applicant's two step method, first a layer 28 of niobium is bondably deposited on the nuclear fuel pellet substrate 26, and then a layer 30 of zirconium diboride burnable poison is bondably deposited on the niobium layer 28 by chemical vapor deposition.
The niobium layer 28 may be applied by conventional means, as previously mentioned, and preferably by relatively fast chemical vapor deposition utilizing niobium pentachloride. The preferred thickness of the niobium layer 28 is between about 3 and 6 microns. Even with a slower conventional non-CVD coating procedure for the niobium layer, the overall coating time for a non-CVD niobium layer plus the CVD zirconium diboride layer will be less than utilizing a sngle step non-CVD zirconium diboride technique, remembering that a single step CVD zirconium diboride layer with the desired thickness will spall.
EXAMPLE
Uranium dioxide fuel pellet substrates 26 were coated by conventional CVD techniques first with niobium and then with zirconium diboride utilizing a vertical tube surrounding vertically stacked fuel pellets. The gaseous CVD precursors (niobium pentachloride for the niobium layer 28, and zirconium tetrachloride and boron trichloride for the zirconium diboride layer 30) were introduced into the bottom of the tube and the by-products were exhausted from the top of the tube. The fuel pellet substrates 26 had been cleaned by light sanding, repeated ultrasonic cleaning in distilled water, and vacuum drying. Thermocouples were mounted on the walls of the tube. The pellet substrates 26 were heated to a thermocouple-measured predetermined wall temperature by an upper furnace while the precursor gases were preheated to a thermocouple-measured preselected wall temperature by a lower furnace. Crack-free coatings were obtained under various conditions as summarized in Table 1. In Table 1, gaseous niobium pentachloride was prepared by vaporizing niobium pentachloride in a hydrogen stream, and gaseous zirconium chloride was prepared by reacting hydrogen chloride and zirconium and carrying the reaction products in a hydrogen stream.
                                  TABLE 1                                 
__________________________________________________________________________
SUMMARY OF CONDITIONS FOR PREPARING Nb/ZrB.sub.2 COATINGS                 
                                              Total                       
         Run Time                                                         
               Temperatures (°C.)                                  
                            Flows (Mole Percent)                          
                                              Flow                        
Run. No.                                                                  
     Layer                                                                
         (min) Gas Preheat                                                
                      Pellet Zone                                         
                            BCl.sub.3                                     
                               HCl                                        
                                  H.sub.2                                 
                                      NbCl.sub.5                          
                                          ZrCl.sub.4                      
                                              (cc/min)                    
__________________________________________________________________________
1    Nb  45    650    850   -- -- 99.921                                  
                                      0.079                               
                                          --  15632                       
     ZrB.sub.2                                                            
         60    600    800   0.140                                         
                               0.053                                      
                                  99.680                                  
                                      --  0.128                           
                                              17098                       
2    Nb  59    650    850   -- -- 99.942                                  
                                      0.058                               
                                          --  17089                       
     ZrB.sub.2                                                            
         37    600    805   0.279                                         
                               0.204                                      
                                  99.298                                  
                                      --  0.220                           
                                              17196                       
3    Nb  44    643    865   -- -- 99.907                                  
                                      0.093                               
                                          --  17136                       
     ZrB.sub.2                                                            
         76    600    800   0.187                                         
                               0.234                                      
                                  99.498                                  
                                      --  0.082                           
                                              17114                       
4    Nb  60    650    840   -- -- 99.942                                  
                                      0.059                               
                                          --  17195                       
     ZrB.sub.2                                                            
         30    605    805   0.279                                         
                               0.204                                      
                                  99.298                                  
                                      --  0.220                           
                                              17196                       
5    Nb  55    650    855   -- -- 99.941                                  
                                      0.059                               
                                          --  17280                       
     ZrB.sub. 2                                                           
         25    600    805   0.279                                         
                               0.204                                      
                                  99.298                                  
                                      --  0.220                           
                                              17196                       
6    Nb  81    650    843   -- -- 99.959                                  
                                      0.041                               
                                          --  17192                       
     ZrB.sub.2                                                            
         27    600    804   0.279                                         
                               0.204                                      
                                  99.298                                  
                                      --  0.220                           
                                              17196                       
7    Nb  27    650    870   -- -- 99.811                                  
                                      0.189                               
                                          --  17112                       
     ZrB.sub.2                                                            
         75    600    825   0.140                                         
                               0.234                                      
                                  99.544                                  
                                      --  0.082                           
                                              17106                       
8    Nb  65    650    843   -- -- 99.920                                  
                                      0.080                               
                                          --  17199                       
     ZrB.sub.2                                                            
         37    602    803   0.279                                         
                               0.204                                      
                                  99.298                                  
                                      --  0.220                           
                                              17196                       
9    Nb  64    650    860   -- -- 99.936                                  
                                      0.064                               
                                          --  17105                       
     ZrB.sub.2                                                            
         55    620    817   0.140                                         
                               0.234                                      
                                  99.543                                  
                                      --  0.082                           
                                              17106                       
10   Nb  71    650    850   -- -- 99.949                                  
                                      0.052                               
                                          --  17194                       
     ZrB.sub.2                                                            
         37    600    810   0.279                                         
                               0.204                                      
                                  99.298                                  
                                      --  0.220                           
                                              17196                       
11   Nb  69    650    848   -- -- 99.956                                  
                                      0.044                               
                                          --  17228                       
     ZrB.sub.2                                                            
         55    600    809   0.140                                         
                               0.105                                      
                                  99.640                                  
                                      --  0.114                           
                                              17101                       
__________________________________________________________________________
Typically, the method of the invention is used to circumferentially surround (i.e., coat only the cylindrical wall of) the uranium fuel pellet substrates 26 with the niobium layer 28 and then the zirconium diboride layer 30. However, in some applications it may be desirable to coat the entire fuel pellet substrate 26, including its top and bottom surfaces. In other applications, it may be advantageous to coat only a portion of the nuclear fuel with the niobium and then coat only a part of the niobium layer with the zirconium diboride. Also, while the method of the invention may be used to produce a fuel pellet 20 having a uranium dioxide containing substrate 26 covered with a niobium containing layer 28 covered with a zirconium diboride containing layer 30, it is preferred that the uranium dioxide containing substrate 26, the niobium containing layer 28, and the zirconium diboride containing layer 30 consist essentially of uranium dioxide, niobium, and zirconium diboride, respectively. As is known to those skilled in the art, the terminology "uranium dioxide containing nuclear fuel" includes mixed uranium-plutonium dioxide.
It will be apparent that many modifications and variations are possible in light of the above teachings. It, therefore, is to be understood that within the scope of the appended claims, the invention may be practiced other than as specifically described.

Claims (10)

I claim:
1. A method for coating a uranium dioxide containing nuclear fuel pellet with a zirconium diboride containing burning poison, comprising:
(a) bondably depositing a layer containing niobium on at least a portion of said nuclear fuel pellet; and
(b) then bondably depositing, by chemical vapor deposition, a layer of said burnable poison on at least a part of said niobium containing layer.
2. The method of claim 1, wherein said nuclear fuel pellet consists essentially of uranium dioxide.
3. The method of claim 1, wherein said niobium containing layer consists essentiallly of niobium.
4. The method of claim 1, wherein said niobium containing layer is deposited by chemical vapor deposition.
5. The method of claim 1, wherein said burnable poison layer consists essentially of zirconium diboride.
6. The method of claim 1, wherein said nuclear fuel pellet comprises generally cylindrical pellets each having a diameter of about one-third inch and a length of about one-half inch.
7. The method of claim 1, wherein said niobium containing layer has a thickness of between about 3 microns and about 6 microns.
8. The method of claim 1, wherein said burnable poison layer has a thickness of between about 8 microns and about 16 microns.
9. In a nuclear reactor fuel assembly having a fuel rod containing a burnable poison coated nuclear fuel pellet, said fuel pellet comprising:
(a) a generally cylindrical substrate containing uranium dioxide;
(b) a bondably deposited layer containing niobium covering at least a portion of said substrate; and
(c) a bondably deposited burnable poison layer containing zirconium diboride covering at least a part of said niobium containing layer.
10. In a nuclear reactor fuel assembly having a fuel rod containing a burnable poison coated nuclear fuel pellet, said fuel pellet comprising:
(a) a generally cylindrical substrate consisting essentially of uranium dioxide;
(b) a bondably deposited layer consisting essentially of niobium circumferentially surrounding said substrate; and
(c) a bondably deposited burnable poison layer consisting essentially of zirconium diboride circumferentially surrounding said niobium layer.
US06/468,743 1983-02-22 1983-02-22 Coating a uranium dioxide nuclear fuel with a zirconium diboride burnable poison Expired - Fee Related US4582676A (en)

Priority Applications (12)

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US06/468,743 US4582676A (en) 1983-02-22 1983-02-22 Coating a uranium dioxide nuclear fuel with a zirconium diboride burnable poison
ZA84504A ZA84504B (en) 1983-02-22 1984-01-23 Coating a uranium dioxide nuclear fuel with a zirconium diboride burnable poison
DE3402192A DE3402192A1 (en) 1983-02-22 1984-01-24 CORE FUEL BODY COATED WITH A COMBUSTABLE NEUTRON ABSORBER
GB08402535A GB2137012B (en) 1983-02-22 1984-01-31 Burnable absorber coated nuclear fuel
SE8400596A SE458810B (en) 1983-02-22 1984-02-06 KERNBRAENSLEKROPP, KAERNBRAENSLEPATRON CONTINUING AND SUCH A BODY AND MANUFACTURED A MANUFACTURED CORNBRAENSLEKROPP
IT19596/84A IT1178463B (en) 1983-02-22 1984-02-14 METHOD FOR COATING A NUCLEAR FUEL OF URANIUM DIOXIDE WITH A BURNING POISON OF ZIRCONIUM DIBORIDE AND NUCLEAR FUEL COATED WITH SUCH METHOD
CH752/84A CH664036A5 (en) 1983-02-22 1984-02-16 WITH A COMBUSTIBLE NEUTRON ABSORBER COATED FUEL BODY.
BE0/212429A BE898971A (en) 1983-02-22 1984-02-21 NUCLEAR FUEL COATED WITH A CONSUMABLE ABSORBER
KR1019840000825A KR910005068B1 (en) 1983-02-22 1984-02-21 Coating a uranium dioxied nuclear fuel with a zirconium diboride burnable poison
FR8402600A FR2541495B1 (en) 1983-02-22 1984-02-21 NUCLEAR FUEL COATED WITH A CONSUMABLE ABSORBER AND MANUFACTURING METHOD THEREOF
JP59030497A JPS59159089A (en) 1983-02-22 1984-02-22 Nuclear fuel coated with burnable absorber
GB08616520A GB2177250B (en) 1983-02-22 1986-07-07 Burnable absorber coated nuclear fuel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US06/468,743 US4582676A (en) 1983-02-22 1983-02-22 Coating a uranium dioxide nuclear fuel with a zirconium diboride burnable poison

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US4582676A true US4582676A (en) 1986-04-15

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US06/468,743 Expired - Fee Related US4582676A (en) 1983-02-22 1983-02-22 Coating a uranium dioxide nuclear fuel with a zirconium diboride burnable poison

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US (1) US4582676A (en)
JP (1) JPS59159089A (en)
BE (1) BE898971A (en)
IT (1) IT1178463B (en)
ZA (1) ZA84504B (en)

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US4695476A (en) * 1985-06-06 1987-09-22 Westinghouse Electric Corp. Process for coating the internal surface of zirconium tubes with neutron absorbers
US4762675A (en) * 1985-06-06 1988-08-09 Westinghouse Electric Corp. Process for coating the internal surface of zirconium tubes with neutron absorbers
US4818477A (en) * 1984-07-10 1989-04-04 Westinghouse Electric Corp. PCI resistant fuel and method and apparatus for controlling reactivity in a reactor core
US4880597A (en) * 1987-08-05 1989-11-14 Combustion Engineering, Inc. Alloy coated fuel cladding
US5319690A (en) * 1992-06-30 1994-06-07 Combustion Engineering Inc. Internal fuel rod coating comprising metal silicates
WO1998009293A1 (en) * 1996-08-27 1998-03-05 A.A.Bochvars All-Russian Scientific Research Institute Of Inorganic Materials Coated nuclear fuel pellet, method for applying this coating and equipment for realising the same
WO2007059851A1 (en) * 2005-11-23 2007-05-31 Technische Universität München Method for producing a fuel element for a nuclear reactor
US7670645B1 (en) * 2003-10-29 2010-03-02 Lsi Corporation Method of treating metal and metal salts to enable thin layer deposition in semiconductor processing
US11587689B2 (en) 2019-10-30 2023-02-21 Battelle Energy Alliance, Llc Nuclear fuel elements including protective structures, and related method of forming a nuclear fuel element

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Cited By (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4818477A (en) * 1984-07-10 1989-04-04 Westinghouse Electric Corp. PCI resistant fuel and method and apparatus for controlling reactivity in a reactor core
US4695476A (en) * 1985-06-06 1987-09-22 Westinghouse Electric Corp. Process for coating the internal surface of zirconium tubes with neutron absorbers
US4762675A (en) * 1985-06-06 1988-08-09 Westinghouse Electric Corp. Process for coating the internal surface of zirconium tubes with neutron absorbers
US4880597A (en) * 1987-08-05 1989-11-14 Combustion Engineering, Inc. Alloy coated fuel cladding
US5319690A (en) * 1992-06-30 1994-06-07 Combustion Engineering Inc. Internal fuel rod coating comprising metal silicates
US5412701A (en) * 1992-06-30 1995-05-02 Combustion Engineering, Inc. Internal fuel rod coating comprising metal silicate
WO1998009293A1 (en) * 1996-08-27 1998-03-05 A.A.Bochvars All-Russian Scientific Research Institute Of Inorganic Materials Coated nuclear fuel pellet, method for applying this coating and equipment for realising the same
RU2131626C1 (en) * 1996-08-27 1999-06-10 Государственный научный центр Российской Федерации "Всероссийский научно-исследовательский институт неорганических материалов им.акад.А.А.Бочвара" Coated nuclear-fuel pellet (versions), method and plant for pellet coating
US7670645B1 (en) * 2003-10-29 2010-03-02 Lsi Corporation Method of treating metal and metal salts to enable thin layer deposition in semiconductor processing
WO2007059851A1 (en) * 2005-11-23 2007-05-31 Technische Universität München Method for producing a fuel element for a nuclear reactor
US11587689B2 (en) 2019-10-30 2023-02-21 Battelle Energy Alliance, Llc Nuclear fuel elements including protective structures, and related method of forming a nuclear fuel element

Also Published As

Publication number Publication date
JPS64670B2 (en) 1989-01-09
IT8419596A0 (en) 1984-02-14
JPS59159089A (en) 1984-09-08
BE898971A (en) 1984-08-21
ZA84504B (en) 1984-09-26
IT1178463B (en) 1987-09-09

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